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WO2009097037A3 - High power density liquid-cooled pebble-channel nuclear reactor - Google Patents

High power density liquid-cooled pebble-channel nuclear reactor Download PDF

Info

Publication number
WO2009097037A3
WO2009097037A3 PCT/US2008/083234 US2008083234W WO2009097037A3 WO 2009097037 A3 WO2009097037 A3 WO 2009097037A3 US 2008083234 W US2008083234 W US 2008083234W WO 2009097037 A3 WO2009097037 A3 WO 2009097037A3
Authority
WO
WIPO (PCT)
Prior art keywords
pebble
reactor
pebbles
nuclear reactor
channels
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Ceased
Application number
PCT/US2008/083234
Other languages
French (fr)
Other versions
WO2009097037A2 (en
Inventor
Per F. Peterson
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
University of California Berkeley
University of California San Diego UCSD
Original Assignee
University of California Berkeley
University of California San Diego UCSD
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by University of California Berkeley, University of California San Diego UCSD filed Critical University of California Berkeley
Publication of WO2009097037A2 publication Critical patent/WO2009097037A2/en
Publication of WO2009097037A3 publication Critical patent/WO2009097037A3/en
Priority to US12/776,599 priority Critical patent/US8744036B2/en
Anticipated expiration legal-status Critical
Ceased legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/07—Pebble-bed reactors; Reactors with granular fuel
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/22—Fuel elements with fissile or breeder material in contact with coolant
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • G21C7/10—Construction of control elements
    • G21C7/107—Control elements adapted for pebble-bed reactors
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

A high-temperature nuclear reactor, cooled by a liquid fluoride salt, is described. The reactor uses an annular fuel pebble comprised of an inert graphite center kernel, a TRISO fuel particles region, and a graphite outer shell, with an average pebble density lower than the density of the liquid salt so the pebbles float. The pebbles are introduced into a coolant entering the reactor and are carried into the bottom of the reactor core, where they form a pebble bed inside a plurality of vertical channels inside one or more replaceable Pebble Channel Assemblies (PCAs). Pebbles are removed through defueling chutes located at the top of each PCA. Each PCA also includes channels for insertion of neutron control and shutdown elements, and channels for insertion of core flux mapping and other instrumentation.
PCT/US2008/083234 2007-11-12 2008-11-12 High power density liquid-cooled pebble-channel nuclear reactor Ceased WO2009097037A2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
US12/776,599 US8744036B2 (en) 2007-11-12 2010-05-10 High power density liquid-cooled pebble-channel nuclear reactor

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US98722207P 2007-11-12 2007-11-12
US60/987,222 2007-11-12

Related Child Applications (1)

Application Number Title Priority Date Filing Date
US12/776,599 Continuation US8744036B2 (en) 2007-11-12 2010-05-10 High power density liquid-cooled pebble-channel nuclear reactor

Publications (2)

Publication Number Publication Date
WO2009097037A2 WO2009097037A2 (en) 2009-08-06
WO2009097037A3 true WO2009097037A3 (en) 2009-11-26

Family

ID=40913458

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/US2008/083234 Ceased WO2009097037A2 (en) 2007-11-12 2008-11-12 High power density liquid-cooled pebble-channel nuclear reactor

Country Status (2)

Country Link
US (1) US8744036B2 (en)
WO (1) WO2009097037A2 (en)

Families Citing this family (18)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US8416908B2 (en) 2011-05-13 2013-04-09 Neal Lawrence Mann Nuclear reactor control method and apparatus
EA033315B1 (en) * 2012-02-06 2019-09-30 Тэррестриал Энерджи Инк. Integral molten salt reactor
US11875906B2 (en) 2012-02-06 2024-01-16 Terrestrial Energy Inc. Method of operating a nuclear power plant
CN103489488B (en) * 2012-06-11 2016-04-13 中国核动力研究设计院 Modular presurized water reactor
EP3031052B1 (en) 2013-08-05 2018-07-25 Terrestrial Energy Inc. Integral molten salt reactor
US9773574B2 (en) * 2013-11-04 2017-09-26 The Regents Of The University Of California Systems and methods for enhancing isolation of high-temperature reactor containments
US10522255B2 (en) 2015-02-19 2019-12-31 X-Energy, Llc Nuclear fuel pebble and method of manufacturing the same
US9786391B2 (en) 2015-02-19 2017-10-10 X-Energy, Llc Nuclear fuel pebble and method of manufacturing the same
CN104916335A (en) * 2015-04-28 2015-09-16 刘紫静 Liquid metal cooling pool type reactor multifunctional in-reactor heat separation system
CA3003498C (en) * 2015-10-30 2024-01-09 Terrestrial Energy Inc. Molten salt nuclear reactor
CN105976879B (en) * 2016-05-09 2019-05-07 中国科学院上海应用物理研究所 A component type molten salt reactor
CA3034283A1 (en) 2016-09-13 2018-03-22 Westinghouse Electric Company Llc Heat pipe molten salt fast reactor with stagnant liquid core
CN108022661B (en) * 2016-10-28 2019-07-09 中国科学院上海应用物理研究所 Discharging method and device of spherical element in fluid medium
KR101787916B1 (en) * 2016-12-30 2017-10-19 한국과학기술원 A nuclear fuel assembly for a thermal neutron reactor
CZ308183B6 (en) * 2017-11-29 2020-02-12 Centrum Výzkumu Řež S.R.O. High temperature nuclear reactor, cooled by molten fluoride salt
CN113299409A (en) * 2021-04-30 2021-08-24 西安交通大学 Small-size villaumite of spiral cross fuel element cools off high temperature reactor core
CN115359933B (en) * 2022-08-17 2023-05-16 西安交通大学 Experimental system and method for flow heat transfer of small-scale fluoride-salt-cooled high-temperature reactor fuel assemblies
CN119943455B (en) * 2025-01-23 2025-09-26 西安交通大学 Method for calculating density of external circulation fuel ball poison nuclei of pebble-bed high-temperature gas cooled reactor

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5439798A (en) * 1977-09-06 1979-03-27 Toshiba Corp Fuel element
WO2002001576A1 (en) * 2000-06-29 2002-01-03 Eskom Nuclear reactor of the pebble bed type
KR100756440B1 (en) * 2006-03-20 2007-09-07 한국과학기술원 Nuclear Fuel Pebble with Shell-type Fuel Zones for High Temperature Gas Cooling Furnaces
KR100772063B1 (en) * 2006-08-29 2007-11-01 한국원자력연구원 Pebble type hot gas reactor with semi-fixed core structure

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE30160C (en) * 1960-01-30 1900-01-01 SOCIETE ANONYME DES TEINTURES ET APPRETS DE ; TARARE in Tarare, Rhone, Frankreich Method and machine for j dyeing fabrics in pieces
US5680424A (en) * 1996-02-28 1997-10-21 Westinghouse Electric Corporation PWR radial reflector

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5439798A (en) * 1977-09-06 1979-03-27 Toshiba Corp Fuel element
WO2002001576A1 (en) * 2000-06-29 2002-01-03 Eskom Nuclear reactor of the pebble bed type
KR100756440B1 (en) * 2006-03-20 2007-09-07 한국과학기술원 Nuclear Fuel Pebble with Shell-type Fuel Zones for High Temperature Gas Cooling Furnaces
KR100772063B1 (en) * 2006-08-29 2007-11-01 한국원자력연구원 Pebble type hot gas reactor with semi-fixed core structure

Also Published As

Publication number Publication date
WO2009097037A2 (en) 2009-08-06
US8744036B2 (en) 2014-06-03
US20100296620A1 (en) 2010-11-25

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